ML20214T340
| ML20214T340 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/29/1987 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8706100214 | |
| Download: ML20214T340 (2) | |
Text
,
es May 3, 1987
- 9 Docket Nos. 50-338 DISTRIBUTION and 50-339 N Dechet,f()e Tech Branch
~
PD22 Rdg.
Gray File Mr. W. L. Stewart S. Varga Vice President - Nuclear Operations G. Lainas Virginia Electric and Power Company D. Miller Post Office Box 26666 L. Engle Richmond, Virginia 23261 OGC-Bethesda E. Jordan
Dear Mr. Stewart:
J. Partlow
Subject:
Projected Values of Material Properties For Fracture Toughness Requirements For Protection Against Pressurized Thermal Shock Events We have reviewed your letters dated January 23, 1986 and November 26, 1986 which were submitted in response to the Pressurized Thermal Shock (PTS) Rule, 10 CFR 50.61, for the North Anna Power Station, Units No. 1 & No. 2 (NA-1&2).
We have found the material properties of reactor vessel beltline materials, the projected' fluence at the inner surface of the reactor vesstil for the end of life of the plant and the calculated RT for the end of life of the plant to be acceptable. The calculated Rf pI5belowthescreeningcriteriaof 270*F at 46.4 and 47.4 effective fel$3ower years of operation for NA-1&2, respectively, both of which are greater than 32 effective full power years (40 calendar years at 80% Icad factor), and, therefore, meets the requirements of the PTS Rule.
The PTS Rule requires that the projected assessment of the RT must be up-dated whenever changes in core loadings, surveillance measurem$dks or other information (including changes in capacity faqtor) indicate a significant change in the projected values.
This ensures that the licensees will track the accumulated fluence for the limiting beltline materials throughout the life of the plant to verify that their assumptions remain valid.
In this regard we re-quest that you submit a re-evaluation of the RT predictedvalueinanyfuturePressure-TemperatN$andcomparisonwithofthe submittals which are sub-mitted as required by 10 CFR 50, Appendix G.
Our associated Safety Evaluation is enclosed.
i s
\\
l 4
8706100214 070529 PDR ADOCK 0500033G P
PDR a
,e
- Mr. W. L. Stewart.
The reporting and/or recordkeeping requirements of this letter affect fewer i
than 10 respondents, therefore OMB clearance is not required under PL 96-511.
l Sincerely,
/s/
Leon Engle, Project Manager Project Directorate II-2 Division of Reactor Projects-I/II j
Enclosure:
As stated cc w/ enclosure See next page i
I i
U, 2
PMr I-b:PDII-2 DP r
LEngle:bg LRubenstein 5/
87 5/y;/87 5/2@/87 I
4
-. y9
--p g-pw- - - -. - - -
m
-9,.9,-
ng
.,y..
p-m-y.
y
..--y 7
y a-,,,
y 7,.
.-c --.
m
.